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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20204B7691999-03-18018 March 1999 Proposed Tech Specs 5.6 Re High Radiation Area.Certificate of Svc,Encl ML20207J0831999-02-11011 February 1999 Proposed Tech Specs for Trojan Isfsi,Stating Length of Time Air Pads Can Be Installed & Inflated ML20151X8671998-09-10010 September 1998 Rev 2 to Proposed TS Bases,Changing Name of Cooling Sys to Modular Spent Fuel Pool Cooling & Cleanup Sys & Updates Spent Fuel Pool Heat Up Info to 3 1/2 Years After Plant Shutdown ML20238E8291998-08-27027 August 1998 Proposed Tech Specs,Deleting Number of License Conditions & TS Requirements as Prerequisite to Implementing Requested Amend to Transfer Nuclear Sf from Existing 10CFR50 Licensed Area to Proposed 10CFR72,ISFSI Area ML20199J5801998-01-29029 January 1998 Proposed Tech Specs Pages,Deleting Security Plan Requirements of 10CFR50.54(p) & Part 73 for Trojan Plant After Spent Nuclear Fuel Is Moved to Proposed ISFSI Area ML20134C9901997-01-28028 January 1997 Proposed Tech Specs 5.0 Re Administrative Controls ML20134A9571997-01-16016 January 1997 Proposed Tech Specs LCO 3.1.4 Re Spent Fuel Pool Load Restrictions ML20134B5881997-01-16016 January 1997 Proposed Tech Specs Deleting Paragraph 2.(C)(7) to Allow Loading & Handling of Spent Fuel Casks & Insertion of New License Condition Authorizing Loading of Spent Fuel & Other Matls in Fuel Building ML20134B8631997-01-16016 January 1997 Proposed Tech Specs Re Delete Paragraph 2.(C)(7) to Allow pre-operational Testing & Load Handling of Spent Fuel Transfer & Storage Casks in Trojan Fuel Building ML20135B5071996-11-27027 November 1996 Proposed Tech Specs Reflecting New Fuel Debris Storage Container Design & Storage of non-fuel Bearing Components & Fuel Rod Storage Container in Trojan ISFSI ML20129E7341996-10-23023 October 1996 Proposed Tech Specs Re Spent Fuel Pool Debris Processing ML20059A5601993-10-21021 October 1993 Proposed Tech Specs Modifying Security License Conditions for Clarity ML20127P2121993-01-27027 January 1993 Proposed TS 6.2.2.f Re Composition of Fire Brigade & TS Table 6.2-1 Re Min Shift Crew Composition for Shift Manager & Noncertified Operator ML20127M6391992-11-16016 November 1992 Proposed Tech Specs for Deferral of Unscheduled Steam Generator ISI ML20141M1901992-03-27027 March 1992 Proposed Tech Specs Re Surveillance Requirements for Lco. Response to Request for Addl Info on Subj Encl ML20059L6701990-09-21021 September 1990 Proposed Tech Spec Table 3.6-1, Containment Isolation Valves ML20247C8941989-07-19019 July 1989 Proposed Tech Spec Table 3.6-1, Containment Isolation Valves ML20245C8091989-06-12012 June 1989 Proposed Tech Specs,Changing Orifice Size of Steam Line Safety Valves Shown in Tech Spec Table 4.7-1, Steam Line Safety Valves Per Loop ML20235L9441989-02-10010 February 1989 Proposed Tech Specs,Allowing Mods to Control Auxiliary Fuel Bldg Complex Resulting in Increase in Lateral Shear Forces on Any Story ML20235Q9191989-02-10010 February 1989 Proposed Tech Specs Re Limiting Conditions for Operation & Surveillance Requirements for Containment Integrity for Equipment Hatches ML20154D1781988-09-0909 September 1988 Proposed Tech Specs Revising Pressurizer LPSI Setpoint ML20151T5951988-08-12012 August 1988 Proposed Tech Specs,Revising Surveillance Requirements for ECCS Check Valves ML20151A0381988-07-0808 July 1988 Proposed Tech Specs Re Radioactive Gaseous Effluents & Radioactive Liquid Waste Sampling & Analysis Program ML20151U7171988-04-14014 April 1988 Revised Proposed Tech Specs Re Plant Sys,As Part of Rev 1 to License Change Application 142 ML20148K5971988-03-23023 March 1988 Proposed Revised Tech Specs Re RCS ML20148C2101988-03-18018 March 1988 Proposed Tech Specs,Reflecting Revised Offsite & Facility Organization Charts ML20196J9031988-03-0101 March 1988 Proposed Tech Specs Modifying OL NPF-1,removing 3.5% U-235 Limit on Reactor Fuel Assemblies & Increase Enrichment Limit for New Fuel Storage Racks to 4.5%.Certificate of Svc Encl ML20147E7371988-03-0101 March 1988 Proposed Tech Specs Re Containment Isolation Valves ML20149K1901988-02-17017 February 1988 Proposed Tech Specs,Adding New Instruments for Monitoring Steam Generator Blowdown Sys Liquid Effluent Radioactivity ML20149L6981988-02-15015 February 1988 Proposed Tech Specs Re Offsite & Facility Organization Charts.Util Certificate of Svc Encl ML20149H1121988-02-0404 February 1988 Proposed Tech Specs Revising Operability & Surveillance Requirements for Component Cooling Water Sys ML20147D4561988-01-15015 January 1988 Proposed Tech Specs,Revising Offsite & Facility Organization Charts ML20195H8971987-12-24024 December 1987 Proposed Tech Specs Deleting Sections Re Fire Protection ML20237D6971987-12-18018 December 1987 Proposed Tech Specs,Requiring Measurement of Initial Discriminator Bias Curve for Each Detector & Subsequent Discrimination Bias Curves Obtained,Evaluated & Compared to Initial Curves ML20237D6551987-12-16016 December 1987 Proposed Tech Specs Deleting Provision for Continued Plant Operation in Section 3/4.4.6.2 & Requiring Prompt Unit Placement in Cold Shutdown After Pressure Boundary Leakage Occurrence ML20236W7611987-11-20020 November 1987 Proposed Tech Specs Including Effects of Nuclear Fuel Design Changes ML20236Q2271987-11-16016 November 1987 Proposed Tech Specs,Resolving Control Room Habitability Issues ML20236P4391987-11-13013 November 1987 Proposed Tech Specs,Extending Surveillance Time Period for Verifying Control Rod Insertability During Control Rod Worth & Shutdown Margin Tests to 7 Days.Certificate of Svc Encl ML20236N3861987-11-0909 November 1987 Proposed Tech Spec,Revising Tech Spec 3.9.9 to Resolve Inconsistencies within Tech Specs.W/Certificate of Svc ML20236N5881987-08-0606 August 1987 Proposed Tech Spec Section, Bases Correcting Section for Agreement W/Definition of Pressure Boundary Leakage ML20235W5571987-07-14014 July 1987 Proposed Tech Specs Re Solid Radwaste Sys ML20215K8381987-06-22022 June 1987 Proposed Tech Spec Table 3.3-1,revising Operability Requirements for Reactor Trip Breakers & 4.3-1,revising Surveillance Requirements for Manual Reactor Trip,Reactor Trip Breakers & Bypass Breakers ML20210B6241987-04-29029 April 1987 Proposed Tech Specs Revising Typos & Clarifying Appropriate Process to Be Used for Review & Approval of Temporary Changes to Procedures.Certificate of Svc Encl ML20209D0251987-04-20020 April 1987 Proposed Tech Specs Re RCS Surveillance Requirements ML20206D9261987-04-0303 April 1987 Revised Tech Spec Pages 3/4 8-6 & 3/4 8-7 Re Onsite Power Distribution Sys,Per License Change Application 128 ML20206A6221987-04-0303 April 1987 Revised Tech Spec Page 7,clarifying License Change Application 124 Re power-operated Valves ML20245A2631987-02-26026 February 1987 Proposed Tech Specs,Consisting of Revised Pages for License Change Application 124 & License Change Application 135, Adding Steamline Isolation Valves & Valve CV-8825 Back Onto Table 3.6-1 & Excluding Containment Airlocks from Criteria ML20211P0031987-02-20020 February 1987 Proposed Tech Specs Re Steam Generator Tube Plugging Criteria in Tube Sheet Region ML20211H4021987-02-11011 February 1987 Proposed Tech Specs Increasing Setpoint Tolerance for Pressurizer & Main Steam Safety Valves from 1% to 2% ML20207Q5371987-01-20020 January 1987 Proposed Tech Specs,Revising Surveillance Requirements for Safety Injection Sys Accumulator Isolation Valves 1999-03-18
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20210M7291999-08-0505 August 1999 Replacement Pages to PGE-1078, Trojan Nuclear Plant License Termination Plan. with D&D Modeling Runs for Determination of Screening Dcgls & Survey Area Maps Indicating Preliminary Survey Units ML20207D3951999-06-0101 June 1999 Rev 1 to Trojan Nuclear Plant Reactor Vessel & Internals Removal Project Transportation Safety Plan ML20204B7691999-03-18018 March 1999 Proposed Tech Specs 5.6 Re High Radiation Area.Certificate of Svc,Encl ML20207J3911999-03-10010 March 1999 Trojan Nuclear Plant License Termination Plan ML20207J0831999-02-11011 February 1999 Proposed Tech Specs for Trojan Isfsi,Stating Length of Time Air Pads Can Be Installed & Inflated ML20153D3081998-09-21021 September 1998 Rev 0 to PGE-1077, Tnp Reactor Vessel & Internals Removal Project Transportation Safety Plan ML20151X8671998-09-10010 September 1998 Rev 2 to Proposed TS Bases,Changing Name of Cooling Sys to Modular Spent Fuel Pool Cooling & Cleanup Sys & Updates Spent Fuel Pool Heat Up Info to 3 1/2 Years After Plant Shutdown ML20238E8291998-08-27027 August 1998 Proposed Tech Specs,Deleting Number of License Conditions & TS Requirements as Prerequisite to Implementing Requested Amend to Transfer Nuclear Sf from Existing 10CFR50 Licensed Area to Proposed 10CFR72,ISFSI Area ML20199J5801998-01-29029 January 1998 Proposed Tech Specs Pages,Deleting Security Plan Requirements of 10CFR50.54(p) & Part 73 for Trojan Plant After Spent Nuclear Fuel Is Moved to Proposed ISFSI Area ML20196J5131997-07-29029 July 1997 Rev 0 to Trojan Second Integrated Test Rept,Filter Media Processing Sys Trojan Nuclear Plant Spent Fuel Pool Debris Project ML20196J5241997-07-29029 July 1997 Rev 2 to In-Canal Equipment,Filter Media Processing Sys, Trojan Nuclear Plant Spent Fuel Pool Debris Project ML20137T9361997-04-0808 April 1997 Rev 1 to Trojan Proof of Principle Test Summary ML20137G1731997-03-20020 March 1997 Rev 6 to Trojan Plant Procedure,Tpp 20-2, Radiation Protection Program ML20137K5151997-03-0404 March 1997 Rev 0 to Trojan Proof of Principle Test Summary ML20138L1901997-01-30030 January 1997 Reactor Vessel & Internals Removal Plan ML20134C9901997-01-28028 January 1997 Proposed Tech Specs 5.0 Re Administrative Controls ML20134B8631997-01-16016 January 1997 Proposed Tech Specs Re Delete Paragraph 2.(C)(7) to Allow pre-operational Testing & Load Handling of Spent Fuel Transfer & Storage Casks in Trojan Fuel Building ML20134B5881997-01-16016 January 1997 Proposed Tech Specs Deleting Paragraph 2.(C)(7) to Allow Loading & Handling of Spent Fuel Casks & Insertion of New License Condition Authorizing Loading of Spent Fuel & Other Matls in Fuel Building ML20134A9571997-01-16016 January 1997 Proposed Tech Specs LCO 3.1.4 Re Spent Fuel Pool Load Restrictions ML20135B5071996-11-27027 November 1996 Proposed Tech Specs Reflecting New Fuel Debris Storage Container Design & Storage of non-fuel Bearing Components & Fuel Rod Storage Container in Trojan ISFSI ML20129E7341996-10-23023 October 1996 Proposed Tech Specs Re Spent Fuel Pool Debris Processing ML20059L1721993-11-30030 November 1993 Final Update to PGE-1043,Amend 3, Accident Monitoring Instrumentation Review, Identifying Rept as Historical by Placing Explanation in Preface to Be Inserted at Front of Document ML20059A5601993-10-21021 October 1993 Proposed Tech Specs Modifying Security License Conditions for Clarity ML20057F1631993-09-30030 September 1993 Updated Trojan Nuclear Div Manual ML20057D9131993-09-30030 September 1993 Amend 14 to PGE-1012, Trojan Nuclear Plant Fire Protection Plan. W/Four Oversize Drawings ML20056F9971993-08-26026 August 1993 Rev 9 to Odcm ML20127P2121993-01-27027 January 1993 Proposed TS 6.2.2.f Re Composition of Fire Brigade & TS Table 6.2-1 Re Min Shift Crew Composition for Shift Manager & Noncertified Operator ML20126B7231992-12-0303 December 1992 Rev 13 to Chemistry Manual Procedure CMP 1, Primary-to-Secondary Leak Rate ML20127M6391992-11-16016 November 1992 Proposed Tech Specs for Deferral of Unscheduled Steam Generator ISI ML20126B7491992-09-25025 September 1992 Rev 7 to Event-Specific Emergency Instruction ES-3.3, Post- SG Tube Rupture Cooldown Using Steam Dump ML20126B7061992-09-25025 September 1992 Rev 7 to Emergency Contingency Action Procedure ECA-3.2, SG Tube Rupture W/Loss of Reactor Coolant - Saturated Recovery Desired ML20126B7331992-09-25025 September 1992 Rev 7 to Emergency Contingency Action Procedure ECA-3.3, SG Tube Rupture W/O Pressurizer Pressure Control ML20126B7411992-09-25025 September 1992 Rev 8 to Event-Specific Emergency Instruction ES-3.2, Post- Steam Generator Tube Rupture Cooldown Using SG Blowdown ML20126B7451992-09-25025 September 1992 Rev 7 to Event-Specific Emergency Instruction ES-3.1, Post- SG Tube Rupture Cooldown Using Backfill ML20126B7601992-09-25025 September 1992 Rev 18 to Emergency Instruction EI-3, SG Tube Rupture ML20126B7181992-09-23023 September 1992 Rev 7 to Emergency Contingency Action Procedure ECA-3.1, SG Tube Rupture W/Loss of Reactor Coolant - Subcooled Recovery Desired ML20126B7141992-08-20020 August 1992 Rev 19 to Off-Normal Instruction ONI-12, High Activity Radiation Monitoring ML20210D5281992-06-0808 June 1992 Errata to Amend 6 to PGE-1025, Environ Qualification Program Manual ML20141M1901992-03-27027 March 1992 Proposed Tech Specs Re Surveillance Requirements for Lco. Response to Request for Addl Info on Subj Encl ML20126B7201992-01-24024 January 1992 Rev 2 to Off-Normal Instruction ONI-3-12, SG Tube Leak ML20062F7391990-11-15015 November 1990 Amend 4 to PGE-1049, Trojan Nuclear Plant Inservice Insp Program for Second 10-Yr Interval,Jan 1987 - Dec 1996 ML20059L6701990-09-21021 September 1990 Proposed Tech Spec Table 3.6-1, Containment Isolation Valves ML20247C8941989-07-19019 July 1989 Proposed Tech Spec Table 3.6-1, Containment Isolation Valves ML20245C8091989-06-12012 June 1989 Proposed Tech Specs,Changing Orifice Size of Steam Line Safety Valves Shown in Tech Spec Table 4.7-1, Steam Line Safety Valves Per Loop ML20247E5331989-03-29029 March 1989 Rev 0 to Procedure QTS-VT-100, Visual Exam Procedure ML20248D3271989-03-27027 March 1989 Rev 0 to QAP-VT-108, Visual Exam ML20247E5491989-03-0202 March 1989 Rev 0 to Procedure TNP-QAP-VT108, Visual Exam ML20235L9441989-02-10010 February 1989 Proposed Tech Specs,Allowing Mods to Control Auxiliary Fuel Bldg Complex Resulting in Increase in Lateral Shear Forces on Any Story ML20235Q9191989-02-10010 February 1989 Proposed Tech Specs Re Limiting Conditions for Operation & Surveillance Requirements for Containment Integrity for Equipment Hatches ML20154D1781988-09-0909 September 1988 Proposed Tech Specs Revising Pressurizer LPSI Setpoint 1999-08-05
[Table view] |
Text
LCA 122
.. Attachment 1 Page 1 of 4 3/4.1 REACTIVITY CONTROL SYSTEMS BASES 3/4.1.1 BORATION CONTROL 3/4.1.1.1 SHUTDOWN MARGIN A sufficient SHUTDOWN MARGIN ensures that 1) the reactor can be made subcritical from all operating conditions, 2) the reactivity transients associated with postulated accident conditions are controllable within acceptable limits, and 3) the reactor will be maintained sufficiently subcritical to preclude inadvertent criticality in the shutdown condition.
SHUTDOWN MARGIN requirements vary throughout core life as a function of fuel depletion, RCS boron concentration, and RCS Tavg. The most restrictive condition occurs at EOL, with Tavg at no load operating temperature, and is associated with postulated steam line break accident and resulting uncontrolled RCS cooldown. In the analysis of this accident, a minimum SHUTDOWN MARGIN of 1.6% Ak/k is initially required to control the reactivity transient. Accordingly, the SHUTDOWN MARGIN requirement is based upon this limiting condition and is consistent with FSAR accident analysis assumptions. With Tavg less than 200*F, the most restrictive reactivity transients resulting from the postulated Boron Dilution Accident are such that a 1.6% Ak/k SHUTDOWN MARGIN is initially required.
3/4.1.1.3 BORON DILUTION A minimum flow rate of at least 3000 GPM provides adequate mixing, prevents stratification and ensures that reactivity changes will be gradual during boron concentration reductions in the Reactor Coolant System. A flow rate of at least 3000 GPM will circulate an equivalent Reactor Coolant System volume of 12,900 cubic feet in approximately 33 minutes. The l reactivity change rate associated with boron reductions will therefore be within the capability for operator recognition and control.
3/4.1.1.4 MODERATOR TEMPERATURE COEFFICIENT (MTC) 1 The limitations on MTC are provided to ensure that the assumptions used in the accident and transient analyses remain valid through each fuel cycle. The surveillance requirement for measurement of the MTC at the beginning,' middle, and near the end of each fuel cycle is adequate to confirm the MTC value since this coefficient changes slowly due l
l TROJAN-UNIT 1 B 3/4 1-1 Amendment No. Ed 8506180494 IB50614 PDR ADOCK 05000344 P PDR l
1 LCA 122 Attachment 1 Pane 2 of 4 PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
- f. At least once per 3 years by performing a flow test of the system in accordance with Chapter 5, Section 11 of the Fire Protection Handbook, 14th Edition, published by the National Fire Protection Association.
4.7.8.1.2 The fire pump diesel engine shall be demonstrated OPERABLE:
- a. At least once per 31 days by verifying:
- 1. The fuel storage tank contains at least 200 gallons of fuel, and
- 2. The diesel starts from ambient conditions and operates for at least 20 minutes.
- b. At least once per 92 days by verifying that a sample of diesel fuel from the fuel storage tank, obtained in accord-ance with ASTM-D270-65, is within the acceptable limits specified in Table 1 of ASTM D975-78 when checked for water, viscosity and sediment.
- c. At least once per 18 months by subjecting the diesel to l an inspection in accordance with procedures prepared in conjunction with its manufacturer's recommendations for the class of service.
4.7.8.1.3 The fire pump diesel starting 24-volt battery bank and charger shall be demonstrated OPERABLE:
- a. At least once per 31 days by verifying that:
- 1. The electrolyte level of each battery is above the plates, and
- 2. The overall battery voltage is >24 volts.
TROJAN-UNIT 1 3/4 7-25 Amendment No. 73, 39, IG A -. . - _.. -. __ __. _ . _ _ ____ __
- LCA 122 Attachment 1 TROJAN NUCLEAR PLANT Page 3 of 4 LOW POPULATION ZONE 2.5 Mile Radius
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LCA 122 2 . .,
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l DESIGN FEATURES a.- In accordance with the code requirements specified in Section
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5.2 of the FSAR, with allowance for normal degradation pursuant to the applicable' Surveillance Requirements,
- b. For a pressure. of_ 2485 psig, and
.c. For a' temperature of '650*F, except for the pressurizer which is 680*F.
-VOLUME 5.4.2 - The total water and steam volume of the Reactor Coolant System is 12,900 i 100 cubic feet-at a nominal Tavg of 584.7'F. l 5.5- ENER6ENCY CORE COOLING-SYSTEMS
. 5.5.1 - The emergency core cooling systems are designed and shall be maintained in accordance with the original design provisions contained in Section'6'.3 of the FSAR with allowance for normal degradation pursuant to the_ applicable Surveillance Requirements.
5.6 FUEL STORAGE CRITICALITY 5.6.1.1 -The fuel storage racks for new fuel are designed and shall be maintained with a nominal 21-inch center-to-center distance between fuel assemblies placed in the storage racks to ensure a Keff of 50.95 with the storage pit filled with unborated water,' and with new fuel containing not more than 44.3 grams of U-235 per axial. centimeter of active fuel assembly (3.5 wt5 enrichment). The criticality analysis includes a conservative allowance for uncertainties as described in Section 4.3.2.7 of the FSAR, as amended through Amendment 26.
. 5.6.1.2 The storage racks for spent fuel are designed and shall be main-tained with a nominal 10.5-inch center-to-center distance between fuel L assemblies' placed in the storage racks to ensure a Keyy 'of $0.95 with the storage pool filled with unborated water and with new fuel containing not more than 57.0 grams of U-235 per axial centimeter of active fuel assembly (4.5 wt5 enrichment)'. The criticality analysis includes a con-servative allowance for uncertainties as described in Section 3.1 of -
PGE-1037.
TROJAN-UNIT.l' 5-5 Amendment No. 25,'3#, di u
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UNITED STATES OF AMERICA ;
NUCLEAR REGULATORY COMMISSION '
l In the Matter of )
)
PORTLAND GENERAL ELECTRIC COMPANY, ) Docket 50-344 THE CITY OF EUGENE, OREGON, AND ) Operating License NPF-1 PACIFIC POWER & LIGHT COMPANY )
)
(TROJAN NUCLEAR PLANT) )
CERTIFICATE OF SERVICE I hereby certify that copies of License Change Application 122 to the Operating License for Trojan Nuclear Plant, dated June 14, 1985, have been served on the following by hand delivery or by deposit in the United States mail, first class, this 14th day of June 1985:
Mr. Lynn Frank, Director State of Oregon Department of Energy Labor & Industries Bldg. Rm 102 Salem OR 97310 Mr. Robert M. Hunt Chairman of County Commissioners Columbia County Courthouse St. Helens OR 97051 l /t G. Zimmerman, Manager Nuc ar Regulation Branch
( Nucl r Safety & Regulation i
l Subscribed and sworn to before me this 14th day of June 1985.
MAlJA Notary Public of gp6gon My Commission Expires: .
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